5th FORUM ON NEW MATERIALS PART B Proceedings of the 5th Forum on New Materials, part of CIMTEC 2010-12 th International Ceramics Congress and 5th Forum on New Materials Montecatini Terme, Italy, June 13-18, 2010

5th FORUM ON NEW MATERIALS PART B......Page 2
Preface......Page 5
Committees......Page 6
Table of Contents......Page 7
Design and Integration of ITER Divertor Components......Page 9
Tungsten as a Structural Divertor Material......Page 19
Microstructural Control for Improving Properties of V-4Cr-4Ti Alloys......Page 30
SiC/SiC Composites Irradiation Behaviour in Fusion Reactor Environment Conditions......Page 35
Experimental Development at a Pilot Plant Scale of a Reduced Activation Ferritic/Martensitic RAFM Steel, Asturfer®......Page 44
Corrosion Experiments of the Candidate Materials for Liquid Lithium Lead Blanket of Fusion Reactor......Page 49
Utilization of Hydride Materials in Nuclear Reactors......Page 59
Progressive Development for Structural Integrity Quantification of Nuclear Grade Graphite in Very High Temperature Gas Cooled Reactor Core Environments......Page 67
Multiscale Modelling of the Influence of Damage on the Thermal Properties of Ceramic Matrix Composites......Page 73
General Corrosion Properties of Modified PNC1520 Austenitic Stainless Steel in Supercritical Water as a Fuel Cladding Candidate Material for Supercritical Water Reactor......Page 80
From High to Low Enriched Uranium Fuel in Research Reactors......Page 86
Simulation and Modelling the Heterogeneous Effects of the Microstructure MOX Fuels on their Effective Properties in Nominal Pressure Water Reactor Conditions......Page 99
Fabrication of Fuel and Recycling of Minor Actinides in Fast Reactors......Page 105
Influence of the Microstructure on the U1-yAmyO2-x (y= 0.1; 0.15) Pellet Macroscopic Swelling......Page 112
Geometrical Aspects of Dislocation-Obstacle Interaction in Iron......Page 117
Quantitative TEM Investigations on EUROFER 97 Irradiated up to 32 Dpa......Page 126
The Influence of Helium and ODS on the Irradiation-Induced Hardening of Eurofer97 at 300°C......Page 132
Advantages Hot Isostatically Pressed Ceramic and Glass-Ceramic Waste Forms Bring to the Immobilization of Challenging Intermediate- and High-Level Nuclear Wastes......Page 138
Synthesis and Properties of Reaction-Bonded SiC Ceramic with Embedded UO2 - TRISO Coated Particles......Page 144
New Actinide Waste Forms with Pyrochlore and Garnet Structures......Page 150
An Innovative Hybrid Process Involving Plasma in a Cold Crucible Melter Devoted to the Futur Intermediate Level Waste Treatment: The SHIVA Technology......Page 156
Development of New Waste Forms to Immobilize Iodine-129 Released from a Spent Fuel Reprocessing Plant......Page 166
Study of New Filters Properties for Cs-137 Vapour Capture at High Temperature......Page 179
Using the Vitrification Test Rig for Process Improvements on the Waste Vitrification Plants......Page 184
Cold Crucible Inductive Melting Technology – Application to Vitrification and Ceramization of High Level and Actinide Wastes......Page 191
Lessons Learned from the Yucca Mountain and WIPP Projects......Page 202
Keywords Index......Page 211
Authors Index......Page 213